가야산국립공원 등산로 및 야영장의 훼손과 주변 자연환경에 대한 이용영향을 파악하기 위해 1989년에 조사를 실시하였다. 등산로폭, 나지노출폭 및 최대 깊이는 이용강도에 따른 차이가 인정되었고, 전체 51개 조사지 점에서 관찰된 훼손형태는 매우 다양하였으며, 훼손된 지점의 등간로 상태중 최대깊이와 등산로물매는 건전한 지점의 상태와 유의한 차이를 보였다. 등산로주변 토양 및 식생인자의 변화경향을 이용영향의 형태에 따라 구분하여 파악할 수 있었고 등산로주변부에 미치는 이용영향은 약 15m에 이르는 것으로 생각된다. 야영장의 훼손은 심각하여 피해도 5등급의 비율이 약 36%이었고 3등급이상인 지역도 약 69%에 달하였다. 야영장에서의 이용활동이 수목의 직경생장을 크게 저해하는 것으로 나타났으며. 종구성의 이질화를 극심하게 진행시키고 있었다. 야영장의 이용강도의 차이나 이용영향의 범위를 파악하는데 적합한 토양 및 식생인자들을 확인할 수 있었으며, 이용간섭의 영향범위는 약 50m이었다. 야영행위에 대한 내성수종은 물푸레나무, 개옻나무, 노린재나무, 국수나무 등이었다.

주진동계인 외팔보의 자유단에 부진동계인 부가질량을 설치하여 부가질량의 크기와 충격 틈새 및 접촉면적을 변화시켜 그때의 진동진폭 특성을 실험함으로써 밝혀진 결과들을 요약하면 다음과 같다. 1) 부가질량의 상하 충격작용이 계의 진동진폭 감소에 상당히 큰 효과가 있으며 일종의 충격감쇠기로써 사용할 수 있음이 실험적으로 확인되었다. 2) 부가질량이 같을 때 충격틈새를 적절히 조정함으로써 진동진폭을 감소시킬 수 있다. 3) 충격 틈새가 일정할 때, 부가질량이 클수록 진동진폭은 감소하지만, 특정 조건에서는 부가질량이 작아도 진폭 감소효과가 크다. 4) 부가질량과 충격틈새가 일정한 조건에서 그 틈새가 작을 때 (1mm, 2mm) 부가질량의 접촉마찰면적이 클수록 진동진폭은 감소한다. 5) 계의 진동진폭 감소가 클 때, 주진동계와 부가질량의 진동진폭에는 위상차가 발생하며 충격감쇠 효과가 가장 클 때 위상차도 최대로 된다. 6) 일반적으로 부가질량이 클수록 진폭은 감소한다. 향후의 연구과제로서 충격시의 소음을 감소시키며 감쇠작용을 증가시키기 위해 접촉면에 적절한 방진고무를 설치하여 그때의 진동 감소 특성을 구명할 것이 요구된다. 이러한 일련의 기초연구를 통하여 목적으로 하고 있는 충격식 동흡진기의 설계 및 이에 대한 실험을 수행할 것이다.

On the slamming analysis of ship design the data for the impact pressure acted on the forward bottom of a ship are needed. Furthermore impact pressure is given by the function of both the hull form coefficient and relative velocity. In this papper. a simplified method to estimate hull form coefficient by perso;,al computer (p. c.) is studied. This numerical analysis was applied to the model of the Mariner type. and then the result by the p. c. was compared with that by IBM 7090 computer. Main results obtained are as follows: 1. The result by the developed p. c. method had fairly good agreement with that by conventional large computer (IBM 7090) within 2% error. 2. This developed method' by p. c. may be applied to the initial estimation of the K-value because of the close agreement between the ship lines by the results of p. c. and that of input.

본 논문에서 얻은 결과를 요약하면 다음과 같다. 1) slamming 충격력에 의한 선각의 굽힘 모우멘트와 전단력의 계산은 본 논문의 이론 전개방법에 의해 구하는 것이 Antonides의 적용 방법보다 더 타당하다고 생각된다. 2) 수치계산 예에서 보면 선체 중앙단면에서 가장 큰 sagging moment가 발생하며 Antonides의 결과치 보다 3~5%정도 더 크게 나타났다. 3) 기준진동형의 중첩항 수는 주어진 문제의 특성 및 요구되는 정도에 따라 결정되어야 하므로 고차 진동형에 대한 실측치와 이론치의 비교 분석이 선행되어야 한다고 생각된다.

1. slam충격수 N(T)는 전부수선에서 거리가 증가할수록 감소하며, N(T)=1인 위치가 제한점으로 되며, 제한점이 되는 위치이후에서는 충격의 영향을 고려치 않아도 무방할 것으로 고려된다. 2. 충격력을 고려한 수직제한깊이는 계획흘수의 1/10로 잡았고, 충격응력에 대해서는 고려된 단면위치에서 압력작용속도의 상이로 인하여, 각각의 단면위치에서 전부선저의 몰입높이에 따라 각각 추정되어야한다. 3. 주어진 단면에 대한 충격력은 압력을 수직한계 높이까지 girth를 따라 계산함으로써 결정할 수 있다. 4. 최대충격력은 전부의 선저판의 형상에 따라 그 작용위치가 달라질 수도 있다. 5. 최대충격력의 약 50% 정도의 힘이 전부선저판의 충격에 소비됨으로, 이는 전부선저판의 적정치수 결정에 도움이 될 것으로 기대된다.

정면규칙파중에서 Bow-flare부 충격은 선저충격에 비해서 작용 시간이 길고, 선체 수직운동진폭이 큰 상태이거나, 파고가 큰 입사파가 적용되는 경우에 선체에 작용하는 충격력은 상당히 크며, 파고가 높아지면, 발생하는 모우멘트도 증가한다. 2. Bow-flare부가 큰 선형의 경우에는 선저노출이 일어나지 않더라도 부가질량의 급격한 증가에 따라 상당히 큰 충격력이 작용한다. 3. Deckwetness, 불규칙파중에서의 응답해석, 상대변위를 구할 때 Dynamic Swell-up의 양을 고려한 계산 등의 검토가 요망된다.

Currently, off-site dose calculations for nuclear power plants are conducted using a computer program (K-DOSE 60). The program is developed based on the regulatory guidelines of the Korea Institute of Nuclear Safety (KINS), which is a domestic nuclear regulatory agency. In this study, a domestic application of the International Atomic Energy Agency (IAEA) TRS (Technical Reports Series)-472 methodology for 3H and 14C in liquid effluents was studied. The dose-evaluation methods adopted and the program configuration for dose evaluation are described based on 3H and 14C in the liquid-effluent-evaluation module of the computer program. The accuracy of the program is verified by comparing the program-calculated results with hand calculation values. Furthermore, a comparative evaluation with LADTAP II, which is a liquid-effluent-evaluation methodology developed by the U.S. NRC (Nuclear Regulatory Commission), is performed. The result confirms that the program-calculated results for the IAEA TRS-472 methodology are consistent with the hand calculation values. Meanwhile, the result of comparative evaluation with LADTAP II indicates different results depending on the methodology used.

This study rigorously investigates the multi-faceted factors influencing consumer purchasing behavior in the emerging retail landscape context and posits a suite of optimization strategies. The paper begins by delineating the current trajectory of the new retail industry, underscoring the pivotal role that big data and artificial intelligence play in the transformative processes of enterprises. The study then explores the salient impact of consumer interaction and brand sentiment on purchasing decisions. Consumers are transitioning from focusing solely on material gratification to a heightened emphasis on psychological and emotional fulfillment, particularly in the information age. Hence, retail businesses should initiate diversified interaction strategies rooted in authentic consumer needs and efficacious brand anthropomorphism to bolster emotional engagement and allure a broader consumer base. Conclusively, the paper offers targeted strategies designed to invigorate consumer purchasing behavior, serving as a substantive guide for optimizing marketing and sales tactics in the novel retail milieu.

Since China put forward the Belt and Road Initiative in 2013, China has actively worked with the Initiative to revitalize relevant regional resources and encourage developing countries to participate in global social governance from a global macro strategic perspective. It should be noted that the initiative has promoted connectivity and exchanges among countries by promoting border infrastructure construction. This strategic direction is in line with Indonesia’s “global marine fulcrum” plan. Moreover, the development of infrastructure construction in Indonesia lags behind. These factors have provided more opportunities and development space for The cooperation between China and Indonesia in the field of infrastructure construction, and the economic cooperation is getting closer and deeper. This paper, based on the relevant data collected in Indonesia from 2003 to 2018, verifies the impact of China’s direct investment on Indonesia’s economic growth by using the method of mediation effect verification and explores the impact of specific approaches.The results show that China’s direct investment in Indonesia can promote local infrastructure construction and promote Indonesia’s economic growth. The two countries proposed future cooperation in areas such as electricity, Internet communication and education infrastructure

Domestic nuclear power plants conduct radiological environmental impact assessments every year in accordance with the Nuclear Safety and Security Commission (NSSC) notice. Among them, gaseous effluents are evaluated for their effects due to inhalation, external exposure in the air, exposure from ground surface deposits, food intake. In order to evaluate the impact of this exposure pathway, an evaluation point for each pathway must be selected. In the case of evaluation points, each country has different evaluation points. In the case of Korea, the evaluation point is calculated on the assumption that one lives 365 days a year at the EAB and consumes food from the nearest production area. In the case of the United States, external exposure and inhalation are evaluated at the site boundary or the nearest residential area, and food intake is evaluated by assuming that food produced in the nearest residential area or the nearest production area is consumed. Currently, the dose evaluation is optimized and selected so that EAB evaluation point for each site includes 16 direction evaluation points for each unit. In the E-DOSE60 program currently under development, the evaluation point was selected by calculating 16 direction x number of units without optimization. The food intake evaluation point was selected as the point that satisfies the minimum farmland area of the U.S. NRC NUREG-1301 and is the shortest distance from the site. The location of the production point from multiple units in included all 16 directions for each unit and quantity of evaluation points was optimized to satisfy the shortest distance. It can contribute to improving the reliability of the E-DOSE60 program currently under development by selecting new evaluation points for evaluating inhalation and external exposure evaluation and selecting optimized dose evaluation points for each site for evaluation by ingestion.

Safety assessments for geological disposal systems extend over tens of thousands of years, taking into account the radiotoxicity decay period of spent nuclear fuel. During this extensive period, the biosphere experiences multiple glacial cycles, and fluctuations in seawater amounts, attributed to the formation and melting of glaciers, lead to global sea level changes known as eustacy. These sea level changes can directly influence the land-sea interface and groundwater flow dynamics, consequently affecting the pathways of radionuclide transport - an essential element of dose assessment. Therefore, this study aims to investigate how glacial cycles and sea level changes impact radionuclide transport within geological disposal systems, especially in the biosphere. To achieve this objective, we obtained climate evolution data including sea level changes for the Korean Peninsula over a 200,000-years, simulated by a General Circulation Model (GCM). These data were then employed to predict site and hydrology evolutions. The study site was conceptualized biosphere of Artificial Disposal System (ADioS), and we utilized the Soil and Water Assessment Tool (SWAT) to simulate hydrological evolution. These datasets, encompassing climate, site, and hydrology evolution, were collectively employed as inputs for the biosphere module of Adaptive Process-Based Total System Performance Assessment Framework (APro). Subsequently, the APro’s biosphere module calculated radionuclide transport in groundwater flow and its release into surface water bodies, considering the influences of glacial cycles and sea level changes. The results show that hydrologic changes due to sea level change are relatively minor, while the impact of sea level change on groundwater flow and discharge is significant. Additionally, we identified that among the water bodies within ADioS, including rivers, lakes, and oceans, the ocean exhibits the most substantial radionuclide outflow throughout the entire period. The spatiotemporal distributions of radionuclides computed within APro will be further processed into a grid format and used as input for the dose assessment module. Through this study, it was possible to determine the impact of long-term glacial cycles and sea level changes on radionuclide transport. Additionally, this module can serve as a valuable tool for providing the spatiotemporal variability of radionuclides required for enhanced dose assessments.

The increasing accumulation of spent nuclear fuel has raised interest in High-Level Waste (HLW) repositories. For example, Sweden is under construction of the KBS-3 repository. To ensure the safety of such HLW repository, various countries have been developing assessment models. In the Republic of Korea, the Korea Atomic Energy Research Institute has been developing on the AKRS model. However, traditional safety assessment models have not considered the fracture growth in the far-field host rock as a function of time. As repository safety assessments guarantee safety for million years, sustained stress naturally leads to the progressive growth of fractures as time goes on. Therefore, it becomes essential to account for fracture growth in the surrounding host rock. To address this, our study proposes a new coupling scheme between the Fracture growth model and the radionuclide transport model. That coupling scheme consists of the Cubic Law model as a fracture growth function and the GoldSim code which is a commercial software for radionuclide transport calculations. The model that adopting such fracture growth functions showed an increase of up to 15% in the release of radionuclide compared to traditional assessment models. our observations indicated that crack growth as a function of time led to an increase in hydraulic conductivity that allowed more radionuclide transport. Notably, these findings show the significance of adopting fracture growth models as a critical element in evaluating the safety of nuclear waste repositories.

Spent nuclear fuel continues to be generated domestically and abroad, and various studies are actively being conducted for interim dry storage and disposal of spent nuclear fuel. The characteristics vary depending on the type of spent nuclear fuel and the initial specifications, and based on these characteristics, it is essential to estimate the burnup and enrichment of spent nuclear fuel as a nondestructive assay. In particular, it is important to estimate the characteristics of spent nuclear fuel with non-destructive tests because destructive tests cannot be performed on all encapsulated spent nuclear fuel in case of intrusion traces in safeguards. Data is made by measuring spent nuclear fuel directly to evaluate burnup of spent nuclear fuel, but computer simulation research is also important to understand its characteristics because past burnup history is not accurately written, and destructive testing is difficult. In Sweden, the dependency of the burnup history in source strength and mass of light-water reactor-type spent nuclear fuel was evaluated, and this part was also applied to MAGNOX in consideration of the possibility of being used to verify DPRK’s denuclearization. SCALE 6.2 TRITON modeling was performed based on public information on DPRK’s 5 MWe Yongbyon reactor, and the source strength of Nb-95, Zr-95, Ru-106, Cs-134, Cs-137, Ce-141, Ce- 144, Eu-154 nuclides were evaluated. Since the burnup of MAGNOX is lower than that of lightwater reactors, major nuclides in decay heat were not considered. The cooling period was evaluated based on 0, 5, 10, and 20 years. In case the discharge timing was different, the total period of discharge and reloading was the same, and the end-cycle burnup was the same, calculations showed that the source strength emitted from major nuclides was evaluated within 2-3% except for Ru-106 and Ce-144 nuclides. Even the burnup step of nuclear fuel is the same, and the reloaded length after discharge is different, i.e., the cooling period between is different at 5, 10, and 20, the source strength of Nb-95, Zr-95, Ce-144, and Cs-137 was evaluated as an error of 1%. Except for Ru-106 and Ce-144, nuclides are highly dependent on burnup. Compared to the case of light-water reactors, the possibility of a decrease in error needs to be considered later because the specific power is low. As a result, radionuclides in released fuel depend on the effects of burnup, discharged and reloaded period, and a cooling period after release, and research is needed to correct the cooling period within the future burnup history. In addition, in this study, it is necessary to select a scenario -based burnup because the standard burnup due to the statistical treatment of discharged fuels was not considered as conducted in previous studies.

The US NRC developed a program called NRCDose3 to evaluates the environmental impact of radiation around nuclear facilities. The NRCDose3 code is a software suite that integrates the functionality of three individual LADTAP II, GASPAR II, and XOQDOQ Fortran codes that were developed by the NRC in the 1980’s and have been in use by the nuclear industry and the NRC staff for assessments of liquid effluent and gaseous effluent, and meteorological transport and dispersion, respectively. Through the integrated program, it is possible to conduct safety assessment and environmental impact assessment from liquid and gaseous effluent when operating permits are granted. In addition to a more user-friendly graphic user interface (GUI) for inputting data, significant changes have been made to the data management and operation to support expanded capabilities. The basic calculation methods of the LADTAP II, GASPAR II, and XOQDOQ have not been changed with this update to the NRCDose3 code. Several features have been added. The previous program used only ICRP-2 dose conversion factor, but the new program can additionally use dose conversion factor of ICRP-30 and ICRP-72. In the previous program, 4 age groups (infant, child, teen, and adult) were evaluated during dose evaluation, but when ICRP-72 was selected, 6 age groups (infant, 1-year, 5-year, 10-year, 15-year, and adult) could be evaluated. In addition, when selecting ICRP-72, many user-modifiable parameters such as food intake and exposure time were added. It will be referred to E-DOSE60, a program currently under development.